ML18114A850

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Reg Guide 1.33,Revision 2, QA Program Requirements (Operation)
ML18114A850
Person / Time
Issue date: 02/28/1978
From:
NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.033, REGGD-1.033, NUDOCS 7907100144
Download: ML18114A850 (17)
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Text

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Revision 2 U.S. N-LEAR REGULATORY COMMISSI.

February 1978 REGULATORY GUIDE

. OFFICE OF STANDARDS DEVELOPMENT ATTACHMENT l REGULATORY GUIDE 1.33 QUALITY ASSURANCE PROGRAM REQUIREMENTS (OPERATION)

A. INTRODUCTION Appendix B, "Quality Assurance Criteria for Nu-clear Power Plants and Fuel Reprocessing Plants, to IO CFR Part 50, "Licensing of Production and Utili-zation Facilities," establishes quality assurance re-quirements for the operation of nuclear power plant safety-related structures, systems, and components.

This regulatory guide describes a method acceptable to the NRC staff for complying with the Commis-sion's regulations with regard to overall quality as-surance program requirements for the operation phase of nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION Subcommittee ANS-3, Reactor Operations, of the American Nuclear Society Standards Committee de-veloped ANSI NIS.7-1972, which contained criteria for administrative controls for nuclear power plants dur-ing operation. This standard, along with ANSI N45. 2-1971, "Quality Assurance Program Require-ments for Nuclear Power Plants," was endorsed by Regulatory Guide 1.33. The dual endorsement was necessary in order for the guidance contained in the regulatory guide to be consistent with the require-ments of Appendix B to 10 CFR Part 50; however, this dual endorsement caused some confusion among users. To clarify this situation, ANSI N18.7-1972 was revised so that a single standard would define the general quality assurance program "requirements" for the operation phase. This revised standard was approved by the American National Standards Com-

. mittee N 18, Nuclear Design Criteria. It was sub-sequently approved and designated N 18. 7-1976/

  • Lines indicate substantive changes from previous issue.

USNRC REGULATORY GUIDES Regul11ory Guides are issued to dftctibe ind make 1vallabl1 to 1h1 publtc methods acceptable to the NRC staff of 1mplemen11ng specific parts of the Commraion'1 rargulat1on1, to delineate 1echniQue1 used by lhe staff 1n evalu111ng sper::1hc prot:lems or PoStul11ed Kcdents, or to provide guidance to ~plicahts. Aegullltory Guides

  • e no, 1Ubsl1tutes for regul1flon1, and comphance w11h them 11 not raquired.

Me1hods and tolu11on1 different from thou 111 out,n the guides will t,e accept*

at>'e,f rttev p,ov,dl a b,1111 for 011 findinrgs raqurliu 10 rhe,uuance or continuance of

  • permir or license by rhl Commic11on.

~mmen11 and suantions fo, improvemen11 in thea gu... ** encouragad at all

"'"* and guidn will be reviud, as 1ppropri1te, 10 accommod1t1 comm.-,11 and to reflecr l"IIIW 1nforma11on o, **p<<*ence.

Tt111 guide wn revilad n a raul1 of a,blt1n1,w comments rece1vad from the pubhc and additional 1taff rr.i.....,.

ANS-3.2, "Administrative Controls and Quality As-surance for the Operational Phase of Nuclear Power Plants," 1 by the American National Standards Insti-tute on February 19, 1976.

There had been some uncertainty with regard to th~

NRC staff's position when a regulatory guide en-dorses, as an acceptable method, the "guidelines" as well as the "requirements" included in a standard.

The NRC staff has evaluated the guidelines contained in N18.7-1976/ANS-3.2 with respect to importance to safety. Revision 1 of this regulatory guide clarified the NRC staff's position on the "requirements" and "guidelines" included in ANSI NlS.7-1976/ANS-3.2. Where conformance to the recommendations of this regulatory guide is indicated in an application without further qualification, this indicates the appli-cant will comply with the "requirements" of ANSI Nl8.7-1976/ANS-3.2,

  • as supplemented or modified by the regulatory position of this guide.

Section I, "Scope," of ANSI NIS.7-1976/ANS-3.2 states that this standard contains criteria for ad-ministrative controls and quality assurance for nu-clear power plants during the operational phase of plant life and that this phase is generally considered to commence with initial fuel loading, except forcer-tain preoperational activities. In this regard, a sepa-rate regulatory guide addressing the quality assurance program for the preoperational phase will be issued.

Other regulatory guides may be issued or this regula-1 tory guide may be revised, if necessary, to amplify the general requirements contained in this standard.

Appendix A to this guide has been further revised as a result of additional comments received on the guide and additional staff review.

'Copies may be obtained from American Nu~le~r Society, S55 Nonh Kensington Avenue, La Grange Park, Ilhno1s 60525.

Comments lhould be,ent to the Secretary of the Comm1uion, US. Nuclear Aegu*

111ory Commiu1on, W.sh1ng1on, O.C. 20555, Attenr,on Oocke11ng and Serv,ce Branch.

Thi guides** issued,n the following ten broilCJ d1v1sions

1. Power Reactors
2. Anurch and Tnt Reactors
3. Fu1l11nd Mat*ials F1cilit1n
4. Erwironman11l 1nd Sil1"9 S. Mater11l11nd Plant Pro11c11on
6. iProducts
7. Tr1ntPOrtilllOn
8. Occup.at 10n1I Health
9. Anr,trust Review
10. Geneul Requests for single copies of 1uued guajes (wtud"I may t,e reµrodueld) or for 1Jli1ce*

ment on an 1utom11,c d11tribu11on list for single copies of future guides 1n specific div11ion1 lhould be made,n wr111ng to the US. Nuclear R99ul*torv Commission.

W11t11ng1on, O.C.

20555, Anen1t0n Direct~. 01v11tOn ol Oocumenl Control.

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C. REGULATORY POSITION The overall quality assurance program require-ments for the operation phase that are included in ANSI NlS.7-1976/ANS-3.2 are acceptable to the NRC staff and provide an adequate basis for comply-ing with the quality assurance program requirements of Appendix B to 10 CFR Part 50, subject to the fol-lowing:

  • 1. ANSI Nl8.7-1976/ANS-3.2 requires the prep-aration of many procedures to carry out an effective quality assurance program. Appendix A, "Typical Procedures for Pressurized Water Reactors and Boil-ing Water Reactors," to this regulatory guide should be used as guidance to ensure minimum procedural coverage for plant operating activities, including re-lated maintenance activities. Appendix A lists typical safety-related activities that should be covered by written procedures but does not provide a complete listing of needed procedures. Many other activities carried out during the operation phase of a nuclear power plant require written procedures not included in Appendix A. Appendix A may also contain proce-dures that are not applicable to an applicant because of the configuration of the nuclear power plant. The procedures listed in Appendix A may be combined, separated, or deleted to conform to the applicant's procedures plan.
2. Throughout ANSI N 18.7-1976/ANS-3.2, other documents required to be included as a part of this standard are identified at the point of reference. The specific acceptability of these standards listed in ANSI Nl8.7-1976/ANS-3.2 has been addressed in the latest revision of the following regulatory guides:

ANSI Standard N45.2 N45.2. I N45.2.2 N45.2.3 N45.2.4 N45.2.5 N45.2.6 N45.2.8 N45.2.9 N45.2. JO N45.2. I I N45.2.13 Nl8. I N 18.17 N 101.4 Regulatory Guide I. 28 1.37 1.38 1.39 1.30 1.94 1.58 I. I 16 1.88 l.74 1.64 I. I 23 1.8 1.17 1.54 Note: N45.2.12 is discussed in NRC documents WASH-I 283, "Guidance on Quality Assurance Requirements During Design and Procurement Phase of Nuclear Power Plants," (Grey Book) and WASH-1309, "Guidance on Quality Assurance Re-quirements During the Construction Phase of Nuclear Power Plants," (Green Book) e and will be endorsed by a regulatory guide upon its approval as an ANSI standard.

3. Section 4. 3.4, "Subjects Requiring [ndepend-ent Review," hem (3) states, in part, that changes to the technical specifications or license amendments re-lated to nuclear safety are required to be reviewed by the independent review body prior to implementation.

lt should be noted that proposed changes to technical specifications or license amendments should be re-viewed by the independent review body prior to their submittal to the Commission for approval.

4. Section 4.5, "Audit Program," of ANSI NIB.7-1976/ANS-3.2 states that audits of selected aspects of operational phase activities shall be per-formed with a frequency commensurate with their safety significance and in such a manner as to ensure that an audit of all safety-related functions is com-pleted within a period of 2 years. In amplification of this requirement, the following program elements should be audited at the indicated frequencies:
a. The results of actions taken to correct de-ficiencies that affect nuclear safety and occur in facil-ity equipment, structures, systems, or method of operation-at least once per 6 months.
b. The conformance of facility operation to pro-visions contained within the technical specifications and applicable I icense conditions-at least once per 12 months.
c. The performance, training, and qualifications of the facility staff-at least once per 12 months.
5. The guidelines (indicated by the verb "should").of ANSI Nl8.7-1976/ANS-3.2 contained in the following sections have sufficient safety impor-tance to be treated the same as the requirements (in-dicated by the verb "shall") of the standard:
a. Section 4.4--The guidelines concerning re-view activities of the onsite operating organization, except the guideline that refers to screening subjects of potential concern.
b. Section 5.2.3-The guideline concerning re-view and updating of standing orders.
c. Section 5.2.4--The guideline concerning re-view, updating, and cancellation of special orders.
d. Section 5. 2. 7. I-The guidelines that address adequate design and testing of replacement parts.
e. Section 5.2.13.4--The guideline concerning special handling tools and equipment.
f. Section 5.2.19(2)-The guideline for check-ing plant operating procedures during the testing pro-gram.
g. Section 5.2.19.l-The guidelines for preop-erational tests, except the guideline that refers to a I.33-2

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L 4.4 run-in period for equi!nt. In addition to these guidelines, the prerequisite steps for each equipment test should be completed prior to the commencement of the preoperational test.

h. Section 5.3.2-The guidelines that describe the content (excluding format) of procedures, except for the guidelines that address ( l) a separate _state-ment of applicability in Section 5.3.2(2), ~2) mcl~-

sion of references in procedures, as applicable, tn Section 5.3.2(3), and (3) inclusion of quantitative control guides in Section 5.3.2(6).

i.. Section 5. 3. 9-The guideline concerning emergency procedures requiring prompt implementa-iion of immediate operator actions when required to prevent or mitigate the consequences of a serious condition.

j. Section 5.3.9.1-The guidelines that describe the content (excluding format) for: the title in Section 5.3.9.1(1); the. inclusion of symptoms to aid in iden-e tification in Section 5.l.9.1(21: auronwic actions in Sectio_n 5.3.9.1(3); immediate operator action, excludmg those guidelines conra1ncd 1n 1he examples, i~ Se~tion ~-3.9.1(4): and subtequeat operator ac-tions tn Section 5.3. 9. 1(5).

D. IMPLEMENT A TlON The purpose of this section is 10 provide informa-tion to applicants and lic:cn1ees rcgan!1n1 the NRC staff's plans for using this rcgul1t"')' gu1Je.

This guide reflects current :-.Re p,-Ktace. There-fore, except in those cases 1ri ~h1ch 1hc applicant proposes an acceptable ahcrn1II\\C mc1hod for com*

plying with the specified pomon, of 1hc Commis-sion's regulations. the mc1hoJ.Jc\\o:ribcJ herein is being and will conrinue 10 be u~J 1n 1hc c~alualion of submittals for opera11ng 11,cn~ applk:111ons until this guide is revised as a rc,ut1 of,uuc~1ons from the public or additional staff fC\\ 1c,-

1.33-3

APPENDIX A TYPICAL PROCEDURES FOR PRESSURIZeo WATER REACTORS AND BOILING WATER REACTORS The following are typical safety-related ac11v111es that should be covered by written procedures. This appendix is not intended as an inclusive listing of all needed procedures since many other activities carried out during the operation phase of nuclear. power plants should be covered by procedures not included in this list.

1. Administrative Procedures
a. Security and Visitor Control
b. Authorities and Responsibilities for Safe Opera-tion and Shutdown
c. Equipment Control (e.g., locking and tagging)
d. Procedure Adherence and Temporary Change Method
e. Procedure Review and Approval
f. Schedule for Surveillance Tests and Calibration
g. Shift and Relief Turnover
h. Log Entries, Record Retention, a*nd Review Procedures
i. Access to Containment
j. Bypass of Safety Functions and Jumper Control
k. Maintenance of Minimum Shift Complement and Call-In of Personnel I. Plant Fire Protection Program
m. Communication System Procedures
2. General Plant Operating Procedures
a. Cold Shutdown to Hot Standby
b. Hot Standby to Minimum Load (nuclear start-up)

C. Recovery from Reactor Trip

d. Operation at Hot Standby
e. Turbine Startup and Synchronization of Generator
f. Changing Load and Load Follow (if applicable)
g. Power Operation and Process Monitoring
h. Power Operation with less than Full Reactor Coolant Flow
i. Plant Shutdown to Hot Standby
j. Hot Standby to Cold Shutdown
k. Preparation for Refueling and Refueling Equipment Operation I. Refueling and Core Alterations
3. Procedures for Startup, Operation, and Shutdown of Safety-Related PWR Systems Instructions for energizing, filling, venting, drain-ing, startup, shutdown, and changing modes of oper-ation should be prepared, as appropriate, for the fol-lowing systems:
a. Reactor Coolant System
b. Control Rod Drive System (including part-length rods)
c. Shutdown Cooling System
d. Emergency Core Cooling System
e. Component Cooling Water System
f. Containment (I) Maintaining Containment Integrity (2) Special Containment Systems (a)* Atmosphere (b) Subatmospheric (c) Double-Wall Containment with Controlled Inters pace (d) Ice Condenser (3) Containment Ventilation System (4) Containment Cooling System
g. Atmosphere Cleanup Systems
h. Fuel Storage Pool Purification and Cooling Sys-tem
i. Main Steam System
j. Pressurizer Pressure and Spray Control Systems
k. Feedwater System (feedwater pumps to steam generator)

I. Auxiliary Feedwater System

m. Service Water System
n. Chemical and Volume Control System (includ-ing Letdown/Purification System)
o. Auxiliary or Reactor Building Heating and Ventilatio.n
p. Control Room Heating and Ventilation
q. Radwaste Building Heating and Ventilation
r. Instrument Air System
s. Electrical System (I) Off site (access circuits)

(2) Onsite (a) Emergency Power Sources (e.g., diesel generator, batteries)

(b) A.C. System (c) D.C. System

t. Nuclear Instrument System

( 1) Source Range (2) Intermediate Range (3) Power Range (4) Incore System

u. Reactor Control and Protection System
v. Hydrogen Recombiner
4. Procedure for Startup, Operation, and Shutdown of Safety-Related BWR Systems l.33-4 0

Instructions for energizing.ling, venting, drain-ing, startup, shutdown, and changing modes of oper-ation should be prepared, as appropriate, for the following systems:

a. Nuclear Steam Supply System (Vessel and Recirculating System)
b. Control Rod Drive System
c. Reactor Cleanup System
d. Liquid Poison System (Standby Liquid Con-trol System)
e. Shutdown Cooling and Reactor Vessel Head Spray System
f. High Pressure Coolant Injection
g. Reactor Core Isolation Cooling System
h. Emergency Core Cooling Systems
i. Closed Cooling Water System
j. Containment (1) Maintaining Integrity (2) Containment Ventilation System (3) Inerting and deinerting
k. Fuel Storage Pool Purification and Cooling System I. Main Steam System (reactor vessel to turbine)
m. Turbine-Generator System
n. Condensate System (hotwell to feedwater pumps, including demineralizers and resin regeneration)
o. Feedwater System (feedwater pumps to reactor vessel)
p. Makeup System (filtration, purification, and water transfer)
q. Service Water System
r. Reactor Building Heating and Ventilation Systems
s. Control Room Heating and Ventilation Systems
t. Radwaste Building Heating and Ventilation Systems
u. Standby Gas Treatment System
v. Instrument Air System
w. Electrical System (1) Off site (access circuits)

(2) Onsite (a) Emergency Power Sources (e.g., diesel generator, batteries)

(b) A.C. System (c) D.C. _System x.. Nuclear Instrument System

( 1) Source Range (2) Intennediate Range (3) Power Range (4) TIP System

y. Reactor Protection System
z. Rod Worth Minimizer e

S. Procedures for Abnonnal, Offnonnal, or Alarm Conditions Since these procedures are numerous and corre-spond to the number of alarm annunciators, the pro-cedures are not individually listed. Each safety-related annunciator should have its own written procedure, which should normally contain (1) the meaning of the annunciator, (2) the source of the sig-nal, (3) the immedate action that is to occur automat-ically, (4) the immediate operation action, and (5) the long-range actions.

6. Procedures for Combating Emergencies and Other Significant Events
a. Loss of Coolant (including significant PWR steam generator leaks) (inside and outside primary containment) (large and small, including leak-rate determination)
b. Loss of Instrument Air
c. Loss of Electrical Power (and/or degraded power sources)
d. Loss of Core Coolant Flow
e. Loss of Condenser Vacuum
f. Loss of Containment Integrity
g. Loss of Service Water
h. Loss of Shutdown Cooling
i. Loss of Component Cooling System and Cool-ing to Individual Components
j. Loss of Feedwater or Feedwater System Failure
k. Loss of Protective System Channel I. Mispositioned Control Rod or Rods (and rod drops)
m. Inability to Drive Control Rods
n. Conditions Requiring Use of Emergency Bora-tion or Standby Liquid Control System
o. Fuel Cladding Failure or High Activity in Reactor Coolant or Off gas
p. Fire in Control Room or Forced Evacuation of Control Room
q. Turbine and Generator Trips
r. Other Expected Transients that may be Applicable
s. Malfunction of Automatic Reactivity Control System
t. Malfunction of Pressure Control System
u. Reactor Trip
v. Plant Fires
w. Acts of Nature (e.g., tornado, flood, dam failure, earthquakes) x.. Irradiated Fuel Damage While Refueling
y. Abnonnal Releases of Radioactivity
z. Intrusion of Demineralizer Resin Into Primary System (B WR Plants)
7. Procedures for Control of Radioactivity (For limit-ing materials released to environment and limiting personnel exposure) 1.33-5

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a. Liquid Radioactive Ate System (I) Collection.

De1fneralizing. Filtering.

Evaporating and Concentrating.

and Neutralizing (2l Sampling and Monitoring

( 3) Discharging to Effluents

b. Solid Waste System

( 1 l Spent Resins and Filter Sludge Handling

(:!l Baling Machine Operation (3) Drum Handling and Storage

c. PWR Gaseous Effluent System

( 1 l Collection. Storage. and Discharge

! 2 l Sampling and Monitoring

( 3 l Air Ejector and Stack Monitoring (4) Ventilation Air Monitoring

d. BWR Air Extraction. Offgas Treatment. and Other Gaseous Effluent Systems (I> \\techanical Vacuum Pump Operation

( 2 J Air Ejector Operation

( 3 l Packing Stearn Exhauster Operation (4) Sampling (51 Air Ejector. Ventilation. and Stack Monitor

e. Radiation Protection Procedures

( J J Access Control co Radiation Areas Includ-ing a Radiation Wo.rk Permit System

( 2 > Radiation Sun*e~ s

( 3> Airborne Radioactivity Monitoring (4> Contamination Control 15 l Respiratory Protection 161 Training in Radiation Protection 17> Personnel \\fonitoring

( 8 l Bioassay Program 19> Implementation of A LARA Program

f. Area Radiation \\tonitoring System Operation
g. Process Radiation \\fonitoring System Operation
h. \\feteorological \\tonitoring
8. Procedures for Control of ~feasuring and Test Equipment and for Sur,eillance Tests, Proce-dures. and Calibrations
a. Procedures of a type appropriate to the cir-cumstances should be pro\\'ided to ensure that tools, gauges. instruments. controls. and other measuring and testing devices are properly controlled, calil:>-

rated. and adjusted at specified periods to maintain accuracy. Specific examples of such equipment to be calibrated and tested are readout instruments. inter-lock permissive and prohibit circuits, alarm devices, sensors. signal conditioners, controls, protective cir-cuits. and laboratory equipment.

b. Specific procedures for surveillance tests. in-spections. and calibrations should be written (imple-menting procedures are required for each surveillance test. inspection. or calibration listed in the technical specifications):

(II Tests Pressu-Water Reactors (al Containment Leak-Rate Tests (bl Containment Isolation Tests (c) Cootainment Local Leak Detection ldl Containment Heat and Radioactivity Removal Systems Tests le) Containment Tendon Tests and Inspections ct) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests

( hJ Fire Protection System Functional Tests

( i) Boric Acid Tanks-Level Instrumenta-tion Calibrations (j I Emergency Core Cooling System Tests (kl Control Rod Operability and Scram Time Tests

( 1 I Reactor Protection System Tests and Calibrations Tests (rn) Permissi,es-Tests and Calibrations (n) Refueling System Circuit Tests

( o) Emergency Boration System Functional (pl DNB Checks and Incore-Excore Flux

\\fonitor Correlations (q) Emergency Power Tests (r) Auxiliary Feedwater System Tests (s) NSSS Pressurization and Leak Detection (t) Inspection of Reactor Coolant System Pressure Boundary

( u I Inspection of Pipe Hanger Settings (v) Control Rod Drive System Functional Tests (w)Heat Balance-Flux Monitor Calibrations Ix I Pressurizer and \\tai n Steam Safety Valve Tests (yl Leak Detection S~scems Tests (zl Axial and Radial Flux Pattern Determi-nations (aal Area. Portable. and Airborne Radiation

\\lonitor Calibrations (bbl Process Radiation Monitor Calibrations (cc I Environmental Monitor Calibrations (dd) Safety Valve Tests (ee) Turbine Overspeed Trip Tests (ff) Water Storage Tanks-Level In-strumentation Calibration (2) Boiling Water Reactors (a) Containment Leak-Rate and Penetration Leak-Rate Tests (b) Containment Isolation Tests (c) Containment Vacuum Relief Valve Tests (d) Containment Spray System Tests (e) Standby Gas Treatment System Teses (including filter tests) t)

1.33-6

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Tests e

(f) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests (h) Fire Protection System Functional Tests (i) Nitrogen Inerting System Tests (j) Emergency Core Cooling System Tests (k) Control Rod Operability and Scram Time (I) Reactor Protection System Tests and Calibrations (m) Rod Blocks-Tests and Calibrations (n) Refueling System Circuit Tests (o) Liquid Poison System Tests (p) Minimum Critical Heat Flux Checks and lncore Flux Monitor Calibrations (q) Emergency Power Tests (r) Isolation Condenser or RCIC Tests (s) NSSS Pressurization and Leak Detection (t) Inspection of Reactor Coolant System Pressure Boundary Tests (u) Inspection of Pipe Hanger Settings (v) Control Rod Drive System Functional (w) Heat Balance

(~) Autoblowdown System Tests (y) Leak Detection System Tests (z) Axial and Radial Flux Pattern Detenni-nations (aa) Area, Portable, and Airborne Radiation Monitor Calibrations (bb) Process Radiation Monitor Calibrations (cc) Environmental Monitor Calibrations (dd) Safety Valve Tests (ee) Turbine Overspeed Trip Test (ff) Water Storage Tanks-Level In.

strumentation Calibrations (gg) Reactor Building lnleakage Tests

9. Procedures for Performing Maintenance

. a. Maintenance that can affect the performance of safety-related equipment should be properly pre-planned and perfonned in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. Skills normally possessed by qualified maintenance personnel may not require detailed step-by-step delineation in a pro-cedure. The following types of activities are among those that may not require detailed step-by-step writ-ten procedures:

(I) Gasket Replacement (2) Trouble-Shooting Electrical Circuits (3) Changing Chart or Drive Speed Gears or Slide Wires on Recorders

b. Preventive maintenance schedules should be developed to specify lubrication schedules, inspec-tions of equipment, replacement of such items as fil-ters and strainers, and inspection or replacement of parts that have a specific lifetime such as wear rings.

e c: Procedures for the repair or replacement of equipment should be prepared prior to beginning work. Such procedures for major equipment that is expected to be repaired or replaced during the life of the plant should preferably be written early in plant life. The following are examples of such procedures for major equipment:

( 1) Repair of PWR Steam Generator Tubes (2) Replacement and Repair of Control Rod Drives (3) Replacement of Recirculation Pump Seals

( 4) Replacement of Important Strainers and Filters (5) Repair or Replacement of Safety Valves (6) Repair of lncore Flux Monitoring System (7) Replacement of Neutron Detectors

d. Procedures that could be categorized either as maintenance or operating procedures should be developed for the following activities. Instructions for these activities may be included in systems procedures.

(l) Exercise of equipment that is nonnally idle but that must operate when required (2) Draining and Refilling Heat Exchangers (3) Draining and Refilling Recirculation Loop (4) Draining and Refilling the Reactor Vessel (5) Draining and Refilling Steam Generators (6) Removal of Reactor Head (7) Disconnection and Reconnection of Wiring Penetrating Reactor Vessel Head (8) Demineralizer Resin Regeneration or Replacement

e. General procedures for the control of mainte-nance,.repair, replacement, and modification work should be prepared before reactor operation is begun.

These procedures should include information on areas such as the following:

(l) Method for obtaining pennission and clear-ance for operation personnel to work and for logging such work and (2) Factors to be taken into account, including the necessity for minimizing radiation exposure to workmen, in preparing the detailed work procedures.

10. Chemical and Radiochemical Control Procedures Chemical and radiochemical control procedures should be written to prescribe the nature and fre-quency of sampling and analyses, the instructions maintaining water quality within prescribed limits, and the limitations on concentrations of agents that may cause corrosive attack ~r fouling of heat-transfer surfaces or that may become sources of radiation hazards due to activation. These procedures should specify laboratory instructions and calibration of lab-oratory equipment. Extreme importance must be placed on laboratory procedures used to determine I.33-7

concentration and species of radioactivity in liquids and gases prior to release, including representative UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 sampling. validity of calibration techniques, and ade-quacy of analyses.

POSTAGE ANO FEES PAIO U.S. NUCLEAR REGULATORY COMMISSION

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6.4 UNIT OPERATING PROCEDURES ATTACHMENT 2 TS 6.4-1 3-1.7-72 Specification A.

Detailed wr~tten procedures with appropriate check-off lists and instructions shall be provided for the following conditions:

1.' Normal startup, operation, and shutdown of a unit, and of all systems and components involving nuclear safety of the station;

2.

Calibration and testing of instruments, component's, and systems involving nuclear safety of the station.

3.

Actions to he taken for specific and foreseen malfunctions of systems or components including alarms, primary system leaks and abnormal reactivity changes.

4.

Release of radioactive effluents

5.

Et:1ergency co_nditions involving potential or actual release of radioactivity

6.

Emergency conditions *involving violation of industrial security.

7.

Preventive or corrective maintenance operations which would have an effect on the safety of the reactor.

8. Refueling operations.

B.

Radiation control procedures shall be provided and made available to all station personnel. These procedures will show permissible radiation exposure. This radiation protection program shall be organized to meet the requirements of 10 CFR 20 and/or the following provisions:

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TS 6.4-2

1.

The intent of 10 CP'R 20.203(c)(2)(iii) ahall be implemented by aatiafying the following conditions:

a.

'l'he entrance to each radiation area in vbich the intensity of., radiation 1a greater than 100 mrem/hr but less than 1000 mrem/br ahall be barricaded and conspicuously posted.

b.

The entrance to each radiation area in which the intensity of radiation 1a equal to or 1reater than 1000 mrem/hr ahall be provided with locked barricade* to prevent

c.
d.
e.

_ unauthorize~ entry into these areas. reys to these locked barricades 1ball be maintained under the administrative control of the Shift Supervisor on duty and/or Superintendent Bealth Phy1ica.

All 1ucb accessible high radiation areas 1hall be 1urveyed by Beal th Physics personnel on a routine achedule, as determined by the Superintendent-Health Phy1ic1, to assure a aafe and practical program.

Any individual entering a high radiation area 1hall have completed the indoctrination courae designed to explain the hazards and aafety requirements involved, or 1hall be e1corted at all times by a person vho has completed the cour1e.

Ally individual or 1roup of individual* permitted to enter a high radiation area per l.d above, ahall be provided with a radiation monitoring device which continuously indicate* the radiation dose rate in the area.

Amendment Nos. 104 and 104

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c.
f.

TS 6.4-3 Entrance to areas with radiation levels in excess of l ll/hr ahall require the use of the "buddy aystem", whereby a minimum of cwo individuals maintain continuous visual and/or verbal communication with each other; or other mechanical and/or electrical means to provide constant communication with the individual in the area shall be provided.

g.

A Radiation Work Permit aystem ahall be uaed to authorize and control any work performed in high radiation areas.

h.

All buildings or structures, in or around which a high radiation area exists, shall be surrounded by a chain-link fence.

The entrance gate shall be locked under admini-atrative control, or continuously guarded to preclude unauthorized entry *.

1.

Stringent administrative procedures 11hall be implemented to assure adherence to the restriction placed on the entrance to a high radiation area and the radiation pro-tection program associated thereto.

2.

Written procedures ahall be established, implemented and maintained covering the activities referenced below:

a.

Process Control Program implementation.

b.

Offaite Dose Calculation Manual implementation.

All procedures described in 6.4.A and 6.4.B, and changes thereto,

  • hall be reviewed and approved by the Station Nuclear Safety and Operating Committee prior to implementation.

Amendment Nos. 104 and 104 I

~-,.

D.

E.

F.

e TS 6.4-4 All procedures described in Specifications 6.4.A and 6.4.B shall be followed.

Temporary changes to procedures described in Specifications 6, 4.A and 6.4.B which do not change the intent of the original procedure may be made, provided such changes are approved prior to implementa-tion by the persons designated below based on the type of procedure to be changed:

1. Administrative
2. Abnormal
3. Annunciator
4. Health Physics
s. Emergency
6. Maintenance
7. Operating
a. Periodic Test
9.

Start-u*p Test

10. Special Test
11. Quality Assurance
12.

Chemistry Cognizant Supervisor Shift Supervisor or Assistant Shift Supervisor Shift Supervisor or Assistant Shift Supervisor

  • Health Physicist Shift Supervisor or Assistant Shift Supervisor
  • Cognizant Supervisor Shift Supervisor or Assistant Shift Supervisor
  • Cognizant Supervisor
  • Engineering Supervisor
  • Engineering Supervisor Manager, Quality Assurance or
  • Supervisor Quality Control
  • Chemist
  • These procedures must have the approval of a licensed Senior Reactor Operator.

Such changes will be documented and aubsequently reviewed and approved by the Station Nuclear Safety and Operating Committee within 14 daya.

Temporary changes to procedures described in Specifications 6. 4.A and 6.4.B which change the intent of the original pro~edures may be made, provided auch changes are approved prior to implementation by the person designated below based on the type of the procedure to be changed.

Amendment Nos. 104 and 104 I

I I

1 -

~-

G.

1. Administrative
2. Abnormal
3. Annunciator
4.

Heal th Physics

s.

Emergency

6. Maintenance
7.

Operating

8. Periodic Test
9.

Start-up Test

10.

Special Test

11. Quality Assurance
12.

Chemistry TS 6.4-5 Station Manager Superintendent - Operations Superintendent - Operations Superintendent - Health Physics Superintendent - Operations Mechanical Supervisor Electrical Supervisor Instrument Supervisor Superintendent - Operations Engineering Supervisor Engineering Supervisor Engineering Supervisor Manager, Quality Assurance or Supervisor Supervisor - Chemistry J

Such changes will be documented and aubsequently reviewed and approved by the Station Nuclear Safety and Operating Committee.

In cases of emergency, operations personnel ahall be a~thorized to depart from approved procedures where necessary to prevent injury to personnel or damage to the facility.

Such changes shall be docu-mented, reviewed and approved by the Station Nuclear Safety and Operating Committee.

Amendment Nos. 104 and 104 l

e TS 6.4-6 H.

Practice of site evacuation exercises shall be conducted annually, following emergency procedures and including a check of coanunications with off-site report groups.

An an.nu.al review of the Emergency Plan will be performed.

I.

The industrial security program which has been established for the station shall be implemented, and appropriate investigation and/or corrective action shall be taken if the provisions of the program are violated.

An annual review of the program shall be performed.

J.

The facility fire protection program and implementing procedures which have been established for the station shall be implemented.

The program shall be reviewed at least once every two years.

K Systems Integrity The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall include the following:

1.

Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2.

Integrated leak test requirements for each system at a frequency not to exceed refu~ling cycle intervals.

Amendment Nos. 72 & 73

L.

M.

e

e.

TS 6.4-7 Iodine Monitoring The licensee shall imi>lement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital area under accident conditions.

This program shall include the following:

1.

Training of personnel,

2.

Procedures for monitoring, and

3.

Provisions for maintenance of sampling and analysis equipment.

Post-Accident Sampling A program shall be established, implemented and maintained which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

1.

Training of personnel,

2.

Procedures for sampling and analysis, 3,

Procedures for maintenance of sampling and analysis equipment.

Amendment Nos.

100 and Nos. 99

I Nuclear Regulatory Comml11lon hl!,ve been satisfied. The program shall take Into account the need for special controls, processes, test equipment, tools, and skills to attain the required quality, and the need for verification of quality by Inspection and test. The program shall provide for Indoctri-nation and training of personnel performln1 activities affectlnl' quality e.s necessary to assure that suitable proficiency Is achieved and maintained. The applicant shall rel'U-la.rly review the status and adequacy of the quality assurance program. Mana.aement of other organizations participating In the quality assurance program shall regularly review the status and adequacy of that part of the qu&llty assurance pro1ram which they are executlnl'.

IIl. 011:SJG!I CONTROL Measures shall be established to assure that applicable regulatory requirements and the desll'Jl basis, a.s defined In t 50.2 and as specified In the license application, for those structures, systems, and components to which this appendix applies are correctly translated Into specifications. drawings, pro, cedures, and Instructions. These measures shall Include provisions to assure that ap.

proprlate quality standards are specified and Included In design documents and that deviations from such standards are con-trolled. Measures shall also be establl:;hed for the selection and review for suitability of application of materials, parts, equip-ment, and processes that are essential to the safety-related functions of the structures, systems and components.

Measures shall be established for the Identification and control of desll'Jl Inter-faces and for coordination amon1 partici-pating design or1anlzatlons. These measures shall Include the establishment of proce-dures among participating design organiza-tions for the review, approval, release, dis*

trlbutlon, and revision of documents Involv-ing desll'Jl Interfaces.

The design control measures shall provide for verlfY!ni or checkln1 the adequacy of desll'Jl, such as by the performance of design reviews, by the use of alternate or simplified calculatlonal methods, or by the performance of a suitable testlnl' prol'?'&JJl.

The verlfyin&' or checlr.ln1 process shall be performed by lndividuala or 1roups other than those who performed the orll'1nal design, but who may be from the same orga-nization. Where a test prol'?"&ffl Is used to verify the adequacy of a specific desll'?l fea-ture In lieu of other verlfyin&' or checluni processes, It shall Include suitable qualifica-tions testinl' of a prototype unit under the most adverse design conditions. Desii?l con-trol measures shall be applied to Items such as the followin&': reactor physics, stress, thermal, hydraulic, and accident analyses; compatibility of materlala; accessibility for e

Part 50, App. I lnservlce Inspection.

maintenance, and repair: and delineation of acceptance crite-ria for Inspections and tests.

Design changes, Including field changes, shall be subject to design control measures commensurate with those applied to the or!1lnal design and be approved by the or1a*

nlzation that performed the original design unless the applicant designates another re-sponsible or1anlzatlon.

IV. PRoc:t7JlDO:!ff OocvKENT COJffJIOL Measures shall be established to assure that applicable re1Ulatory requirements, design bases, and other requirements which are necessary to assure adequate quality are suitably Included or referenced In the docu-ments for procurement of material, equip-ment, and services, whether purchased by the applicant or by Its contractors or sub-contractors. To the extent necessary, pro-curement documents shall require contrac-tors or subcontractors to provide a quality assurance proimun consistent with the per, tlnent provisions of this appendix.

V. INS'ffltl'CTIO!IS, PROCEDURES, Affl>

DMWJ!IGS Activities affectlnl' quality shall be pre-scribed by documented Instructions, proce, dures, or draWlnl's, of a type appropriate to the circumstances and shall be accom-plished In accordance with these Instruc-tions, procedures, or drawings. Instructions, procedures, or drawlnp shall Include appro-priate quantitative or qualitative acceptance criteria for dete~ that Important ac-tivities have been satisfactorily accom-plished.

VI. Doctl'xENT CONTROL Measures shall be established to control the Issuance of documents, such as lnstruc, tlons, procedures, and drawings, Including ch&n1es thereto, which prescribe all activi-ties &ffectlng quality. These measures shall assure that documents, lncludin&' changes, are reviewed for adequacy and approved for release by authorized penionnel and are dis*

trlbuted to and used at the location where the prescribed activity Is performed.

Chan1es to document.a shall be reviewed and approved by the same or1anl.zatlons that performed the orlrtnal review and ap.

proval unless the applicant desll'?lates an-other responsible orsaruzatlon.

VII. CONTROL or Ptl'RCHASED MATERIAL.

EQtl'JPIIDT, Affl> SERVICES Measures shall be established to assure that purchased material, equipment, and services, whether purchased directly or throu1h contractoni and subcontractors, conform to the procurement documents.

These measures shall Include provisions, as 551 ATTACH~1ENT 3

Part 50, App. I appropriate, for source evaluation and selec-tion. objective evidence of quality furnished by the contractor or subcontractor, Inspec-tion at the contractor or subcontractor source, and examination of products upon delivery, Documentary evidence that mate-rial and equipment conform to the procure-ment requirements shall be available at the nuclear powerplant or fuel reprocessln1 plant site prior to Installation or use of such material and equipment. This documentary evidence shall be retained at the nuclear

  • powerplant or fuel reprocessln1 plant site and shall be sufficient to identify the specif.

le requirements, such &s codes, standarda, or specifications, met by the purchased materi-al and equipment. The effectiveness of the control of quality by contractors and sub-contractors shall be assessed by the appli-cant or deslsnee at Intervals consistent with the Importance, complexity, and quantity of the product or services.

VIII. lDENTincAnOlf AND COMTROL OP MATERIALS, PARTS, AND COMPONENTS Measures shall be established for the identification and control of materials, parts, and components, lncludln1 partially fabricated assemblies. These measures shall assure that Identification of the Item Is maintained by heat number, part number, serial number, or other appropriate means, either on the Item or on records traceable to the Item, as required throu1hout fabrica-tion, erection, Installation, and use of the Item. These Identification and control meas-ures shall be deslsned to prevent the use of incorrect or defective material, parts, and components.

IX COMTROL or SPECIAL PROCESSES Measures shall be established to assure that special processes, lncludln1 welding, heat treatln1, and nondestructive testln1, are controlled and accomplished by quali-fied personnel usln1 qualified procedures In accordance with applicable codes, standards, specifications, criteria, and other special re-quirements.

X. IlfSPECTIOlf A program for inspection of activities af.

!ectlng quality shall be established and exe-cuted by or for the orpnlzatlon perfonnlna the activity to verify conformance with the documented Instructions, procedures, and drawln,s for accompllshln1 the activity, Such Inspection shall be performed by Indi-viduals other than those who performed the activity being Inspected.

Examinations, measurements, or tests of material or prod-ucts processed shall be performed for each work operation where necessary to assure quality. U Inspection of processed material or products Is Impossible or disadvanta-geous. Indirect control by monitoring proc-ATTACHMENT 4 10 CFI Ch. I (1-1-81 Edition) essin, methods. equipment, &nd penonnel shall be provided. Both Inspection and proc-ess monltorln1 shall be provided when con-trol Is Inadequate Without both. U mandato-ry Inspection hold points, which require wtt-nessln1 or lnspectln1 by the applicant's des-lsnated representative and beyond which work shall not proceed without the consent of Its deslsnated representative are re-quired, the specific hold points shall be Indi-cated In appropriate documents.

XI. TuT COlffllOL A test proirram shall be established to assure that all testlnl required to demon-strate that structures, systems, and compo-nents will perform satisfactorily In service la Identified and performed In accordance with written test procedures which Incorporate the requirements and acceptance limits con-tained In applicable deslsn documents. The test pro,ram shall Include, as appropriate, proof tests prior to Installation, preopera-tlonal tests, and operational teats durini nu-clear power plant or fuel reprocesalnl plant operation, of structures, syStems, and com-ponents. Test procedures shall Include pro-visions for assurln1 that all prerequisites for the gtven test have been met, that adequate test Instrumentation la available and used, and that the test Is performed under suita-ble environmental conditions. Test results shall be documented and evaluated to assure that test requirements have been sat-isfied.

XII. COtffaOL or Mu.stl"II.INO A1'1) TuT EQUIPMENT Measures shall be established to usure that tools, sages, Instruments, and other measurtn1 and testing devices used In activi-ties affectln1 quality are properly con-trolled, calibrated, and adjusted at specified periods to maintain accuracy within neces-sary limits.

XIII. H.umLINO, STOllAOI: A1'1> SBIPPI110 Measures shall be established to control the handlina, stora1e, shlppln1, cle&nlnl and preservation of material and equipment In accordance wtth work and Inspection In-structions to prevent dama,e or deteriora-tion. When necessary for particular prod-ucts, special protective environments, such as Inert,as atmosphere, specific moisture content levels, and temperature levels, shall be specified and provided.

XIV. INSPEC1'I01f, TuT, AM> 01'1:RAnJfO STATUS Measures shall be established to Indicate.

by the use of muklngs such as stamps, tap, labels, routing carda, or other suitable means, the status of Inspections and tests performed upon Individual Items of the nu-552

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